• 专利附录
  • 专利说明
  • 权利要求
  • 类似技术
  • 同族专利
  • 引用文献
  • 法律状态
  • 优先权
    • 专利摘要:
    This invention relates to a standard component 99mTC elution generator useful for medical purposes and consisting of prefabricated component parts. The main generator column of the device may be used both as an irradiation container and an elution container, enabling the user to supply activated or nonactivated parts. The main generator column made from by neutrns little activable materials serves first as reactor irradiation ampoule and after having been activated in the reactor by neutrons and after a simple adjustment serves directly as the generator column. It is filled with water insoluable molybdates or polymolybdates (with the molybdenum content in the range 10-40%), easily releasing 99mTc generated by radioactive decay of the mother 99Mo formed in it by neutron activation. This column filling serves originally as target material for reactor irradiations and afterwards it is directly used as the generator elution matrix. Accordingly, all components of the generator can be produced in a "ready-to-use" form and supplied as inactive material. When nonactivated parts are used, activation is performed on-site by a local reactor. The use of nonactivated parts is advantageous because they are more easily and more safely manufactured and transported. The invention further provides for efficient generation of 99mTC radionuclides from medium neutron flux irradiation of molybdenum in a natural isotopic mixture.
    公开号:SU1702436A1
    申请号:SU857773826
    申请日:1985-05-13
    公开日:1991-12-30
    发明作者:Свобода Кристиан；Мелихар Франтишек；Шебек Зденек；Тымпл Милан
    申请人:Институт Ядерных Исследований (Инопредприятие)；
    IPC主号:
    专利说明:

    The invention relates to turf medicine, namely to the manufacture of prefabricated
    generator Tc.
    The modern development of turf medicine requires the delivery of generators with a total activity of at least 4 GBq, but usually 8 GBq, sometimes larger than 40 GBq. An eluent generator is known, in which alumina is used as a sorption material, the sorption capacity of which is several weight% Mo . This makes it possible to irradiate molybdenum with natural content of isotopes in reactors with an average intensity of neutron flux, i.e. 1017 1018n / m2 s, to prepare generators with a total activity of several hundred MBq, which is not enough for normal use. Therefore, it is necessary to use as a target material or enriched Mo from reactors with high intensity neutron flux, or prepare Mo without carrier by dividing uranium. Both of these methods require large capital expenditures; therefore, a high-performance reactor or a complex of laboratories is used to process highly active irradiated uranium and to eliminate the twenty-fold activity of fission products after 99Mo separation.
    At the same time, these methods are very laborious. For some countries, these methods are not available. In such cases, fundamentally different chemical processes are used to separate the MTs from the parent Mo, in which lower specific activity does not interfere. Either mts sublimation from a suitable S9Mo compound or extOOm is used.
    Tc with methyl ethyl ketone from sypno-basic aqueous solution of 99Mo molybdenum-acid salt. Although both methods make it possible to use active material obtained by irradiating molybdenum in a natural isotopic mixture in reactors with medium and even low neutron flux, i.e. about
    1016 - 5
    179
    10 n / m with, however, their
    the disadvantage is the complexity of the equipment and the great complexity of obtaining
    Tc than a conventional washout generator. Therefore, in most cases, these methods are successfully applied only for production in nuclear research centers, from which a ready-to-use technetium solution is delivered to the nearest hospitals.
    Tc..Hot and miniature versions of both types of generators, suitable for operation in hospitals, extraction or sublimation, were developed, but their implementation is difficult due to the large labor intensity of separation.
    In recent years, research has emerged in which, instead of alumina, it was proposed to use other materials as a generator sorption matrix, which would contain a much larger amount of molybdenum and from which it would also be possible to wash out MTs with a large yield (Evans IV, Moors PV, Soddeau, IM A New Generator for Tc. - Sat.Ill, World Congress on Nuclear Medicine and Biology, Paris, 1982, pp. 1592-1595). This type of generator is based on a zirconium molybdate generator sorption matrix obtained by dissolving irradiated molybdenum oxide in an alkali solution, precipitating
    zirconium nitrate and drying at 105 ° C. The obtained zirconium molybdate with an approximate composition of Zr02 MoO xH20 and an approximate content of 25 wt.%
    Molybdenum hydration was transferred to a form that made it possible to flush out 9mTs, which arose during the decay of 99Mo, with an efficiency of 70-90%.
    At present, similar experiments with comparative results have been carried out, in addition to zirconium molybdate and titanium molybdate, in which the elution efficiency of 99 mTs of 50-80% was achieved. Was tested by vymyvagelna
    5 matrix with a content of 10-40 wt.% Molybdenum. The best results were obtained with preparations containing 20-30 wt.% Molybdenum. In this case, the samples were not dried at 105 ° С and special hydration, but only dried at low temperatures.
    temperatures, i.e. . Further
    leaching experiments were tested
    MTs from the matrix that was first
    obtained by irradiation in a neutro5 reactor by us. The target material was both zirconium molybdate and tigane molybdate. Preparations before irradiation were subjected to prolonged drying at room temperature. A particle size of 50-140 microns was used. The elution efficiency achieved l jMTc ranged from 40 to 80%.
    These results created theoretical
    5 prerequisites for the creation of a new type of wash-out prefabricated generator, which would consist of parts manufactured in advance in an inactive form, and after irradiation by simple manipulation would prepare
    0 for the washout process. Such a generator should eliminate the following disadvantages of the known methods of obtaining mTS:
    limited availability of the enriched J Mo isotope and reactors with high neutron current:
    investment and operational requirements for the preparation of Mo-based wash-out generators from fission products;
    0 problems associated with the control of used fission products;
    the laboriousness and high cost of eliminating fission products arising as a by-product;
    5 increased risk of environmental contamination;
    relatively more complex and more long-lasting methods for obtaining mTS by the extraction or sublimation process;
    transportation problems in the supply of technetium from central generators .;
    the difficulty of introducing into the course of a sublimation or extraction generator in a miniature design in hospitals;
    the inability to use a reactor with a neutron flux below 1 1018 n / m3 s for the manufacture of a washout generator with activities greater than 2 GBq. based on Mo obtained by the reaction (p,
    Do):
    great laboriousness and demands for laboratory equipment with the present methods of manufacturing washing generators;
    the need for additional sterilization; significant transportation costs, and sometimes the difficulty of locating more parcels in an airplane, especially when it is necessary to transport entire generator sets to remote locations.
    The purpose of the invention is to create a technetium-99gp elution generator, which makes it possible to carry out the majority of technological operations prior to irradiating the target material with a neutron flux.
    These shortcomings of the present solutions eliminate the new type of washout generator, the essence of which is that the main generator extraction vessel is made of a material that is little activated by neutrons, and is equipped with two outlets with porous seals and easily eliminating gates. The vessel is filled with coarse dispersion material with a high content of molybdate, which makes it possible to first use the vessel as an ampoule during irradiation, and its filler as the target material, and after irradiation in the reactor, directly use it as a washout eluting column, and the filler as an elution matrix mts. The filler of the main wash-out generating vessel is a material on the surface of which molybdenum is not sorbed, but is directly included in the chemical skeleton, which makes it possible to easily wash out the MTF that appeared in the matrix during radioactive decomposition of Mo. Such materials are water-insoluble molybdates or polymolybdates, the cations of which are formed by ions of elements that are poorly activated by neutrons, for example, zirconium or titanium.
    The advantage of a new type of collecting wash-out generator is also manifested in the method of its manufacture, in that the main washing-out generating vessel is still in an inactive state before being activated by the neutrons in the reactor and filled with a wash-out matrix and adapted for use as an irradiated ampoule in the reactor, and after simple installation - as the main column of the generator. In this way, the prepared main generator washing tank with closed outlets is irradiated in the reactor. In this case, in its filler, i.e. in the skeleton of the matrix, when activated by neutrons, radioactive Mo atoms appear. generating Tc. After being removed from the reactor, the outlet gates are opened and the remaining generator components are connected with hoses. In the manufacture of the generator in
    In sterile version, all generator components are pre-sterilized and protected from secondary bacterial contamination, and installation after irradiation is carried out under antiseptic conditions. In order to sterilize the main wash-out generating vessel, radiation sterilization is used, which occurs as an accompanying phenomenon when it is irradiated in a nuclear reactor.
    0 Figure 1 shows the basic kit.
    combined washout generator; figure 2 is a generator in assembled form.
    The main washing-out generating vessel 1 is, as a rule, made of cylindrical form with an inlet of 2 and an outlet of 3 and has a volume from several millimeters to several tens of millimeters. The vessel is made of a material that is little activated by neutrons and is corrosion resistant, such as zirconium, aluminum. The vessel is filled with the target material 10 in an amount of more than 10 wt.% Molybdenum, which provides an effective selective leaching of MTF that occurred during the decomposition
    5 Mo As a rule, these are powdered or granulated molybdates or polymolybdates of zirconium, titanium or other elements that are poorly activated by neutrons. The target material in the vessel is fixed
    0 seals 8 and 9. As a fixing material, materials that are weakly activated by neutrons and prepared in a porous form are used so that they hold the fine-grained material of the target and at the same time are well-permeable to the scrubbing solution. Such materials are, for example, porous sintered silica or zirconia, graphite felt, fibrous extruded mixture of silicon and aluminum.
    The generator can be prepared in such a way that radiation sterilization also takes place simultaneously with neutron activation in the reactor. Before investing in the reactor, the drive and discharge tubes are blocked, for example, by sealing, mechanical fusing with aluminum gasket, screwing the gates 4 and 6 with aluminum gasket 5 and 7. If necessary, the whole vessel can still be wrapped in aluminum foil, which acts as protection against secondary bacterial contamination after removing from the reactor to antiseptic connection of connecting tubes or hoses 11 and 12. After irradiation in the reactor, the tubes of the main generating column are opened, for example, from they are sawn, cut off or unscrewed in a sterile and protected box, and pre-sterilized matching tips, underwater and discharge hoses or tubes 11 and 12 are attached to them. The opposite tips of these leads remain protected by packaging or stopper from bacterial contamination. The main generator column, together with the supply lines, is placed in the primary lead transport container 13. The container may be made of lead or uranium depleted in JU. The inlet 11 and outlet 12 tubes are inserted into the corresponding openings in the container 13 or in its lid 14 so that they do not interfere during transport. The tips of these tubes are sealed with plugs or packaging and protected from bacterial contamination. The primary container is covered with a lead cap 14, which has a spherical protrusion for manipulation. The lid is attached to the container body with two screws or another suitable method, for example, two worn right-angle hoops. After being plugged into the rigid shell, this main part of the generator is sent to the consumer.
    Other parts of the generator set are periodically sent to the customer in advance, which are sterilized in advance and protected from secondary bacterial contamination. This is a pyrogenic wash solution reservoir 15 (plastic bag or bottle with an antiseptic guarded air inlet, or injection syringe), safety column 16 filled with a suitable sorbent, for example, zirconium oxide, aluminum, superimposed head 17 with attached hose, bottles 18 for eluate in the lead casing 19. In addition, the laboratory lead protective case 20 and the head part of the generator 21 are supplied to the consumer once for accommodating the connecting parts of the kit. At the consumer
    after being removed from the shell, the container 13 is placed in a laboratory housing 20 made of lead or depleted uranium in the form of a strong-walled pot. Uncork the tips of the tubes; The supply 11 is connected to the tank 15 with a sterile saline solution in an antiseptic manner, and the outlet 12 to the set of a protective column 16 connected to a pinhead 17
    penicillin bottles 18 for the eluate, which are placed in a protective thin-walled lead casing 19. All these parts of the installation are fixed in the cylindrical head of the generator 21, which has recesses for positioning the individual parts. The head of the generator itself is planted in a circular cut-out in the laboratory housing 20. The leaching is carried out in such a way that, if necessary,
    the evacuated penicillin bottle is placed on the puncture head and the corresponding part of the saline solution from the reservoir 15 is absorbed through the main washout
    generator vessel 1 and protective column 16 in a penicillin bottle. After the elution has been performed, the puncturing needle in the head is protected from bacterial contamination by puncturing the non-evacuated
    sterile penicillin bottle. It is usually assumed that individual parts will be mounted directly to the consumer. The generator head with parts already mounted and the attached main generator vessel in the primary container can be supplied as a generator set that the user will only place in the laboratory building.
    This requires a small rework of the head part of the generator 21 and the cover 14 so that they are rigidly connected, for example, by means of a mutually screwing rod
    Achieved activity in the new type
    generator with a content of 25 wt.% Mo in the target material, which is also a washed out matrix, with a bulk density of 1 g / ml, for different volumes of the main generator column and the intensity of the neutron flux are given in the table. Activities are related to Mo. by a stopping time of 72 hours after termination of the irradiation with the preceding continuous irradiation for 90 h.
    In the case when the main leaching generating vessel is made of zirconium, not only the filler is activated, but also the own material of this vessel. Due to weight ratios (approximately 10 x more Zr than Mo), activating sections, irradiation time and extinction, the main generator vessel also has 7Zr activity with a decay half-period of 17 hours, approximately comparable to Mo activity. By the end of irradiation, this activity does not exceed twice the value of 99Mo, and by the conditional time it is already only 20%. The vessel also has a 95Zr activity with a 64 day decay half-life period in equilibrium with a 95Nb daughter with a 35 day decay time period. which is approximately 10% Mo activity by the end of the irradiation and 20% activity by the conditional time. This fact does not cause significant difficulties in designing the generator protection. In the case when the main generator vessel is made of aluminum, these values are significantly lower, since only Zr is activated in the target material, the weight amount of which is substantially less than in the vessel material. Numerically pure aluminum does not produce any interfering products when irradiated with neutrons, since the short-lived AI with a disintegration half-life of 2.2 min completely disintegrates before the generator operates on its own. But here, as a rule, the contaminants are activated and, moreover, when (n, a) the reaction on fast neutrons, sodium Na occurs (a decay half-period of 15 hours). From the radiation point of view, the most advantageous material for the manufacture of the main washing generator vessels is quartz, in which only Si is activated (2.6 hours) and, moreover, with a low yield. The pollution content is usually also quite low. Quartz is also highly resistant to chemicals and its only drawback is brittleness.
    A neutron flux of 1,101 n / m s corresponds to a radiation dose of 360 kGy / h. At doses greater than 30 kGy, all microorganisms and their latent forms are destroyed. This means that with extremely low neutron fluxes that are almost unsuitable for neutron activation of generators, reliable radiation sterilization of the vessel and its filler is achieved during irradiation, which lasts more than 1 hour.
    This precludes additional sterilization, for example, in a steam autoclave. However, it is necessary to prevent secondary bacterial infection during the losleradiation transport and installation of the generator set, which is done by creating protective coatings for the main column and mounting in antiseptic conditions.
    Example 1. In the simplest laboratory version, the main washout generating vessel is made of a quartz tube, which at both ends
    5 is conically tapered into narrow tubes that are sealed or plugged with an aluminum plug. The vessel is filled with a target material consisting of zirconium molybdate, dried at 60 ° C with a grain size of
    0 100 to 150 microns, and the material is sealed in narrow places with quartz wool. The vessel before irradiation in the reactor is wrapped in aluminum foil. After irradiation, the constricted portions of the tubes are incised with a knife or
    5 file and break off or uncork. Before this, it is possible to eliminate possible bacterial contamination from the ends of the tubes by careful burning in the flame. Hoses, best of silicone rubber, are attached to the cut off tubes. The vessel is protected from radiation during operation, for example, in a primitive version with several skeins of sheet lead, or it can be placed
    5 into a simple lead container with central openings for the passage of hoses,
    Attached to the hose column is a washing solution reservoir, which may be a burette, a separatory funnel,
    0 bottle for infusion solution, injection syringe, etc. The eluate may drip either into a beaker, or into a penicillin bottle with an evacuated needle, or into an evacuated bottle.
    Fig. 5: Figure 2. The main washing-out generating vessel is a hollow cylinder made of aluminum or zirconium with a section to height ratio of 1: (2-5). At both ends
    0 identical flanges and tips of narrow tubes, which are equipped with threading, are attached, caps, on the inner side of which, are screwed onto cutting tubes. There is an aluminum foil seal. The target material is placed in the column. for example, titanium molybdate, dried at 40 ° C, grain size from 70 to 150 microns, i.e. fractions from 100 to 200 Mesh. The caps are unscrewed from the column after irradiation in an antiseptic box and screwed on.
    99m-,
    the sterilized tips of the supplies of the washing system, thus the prepared vessel was used to make up the generator by connecting it to the rest of the kit.
    The washing assembly generator Tc according to the invention, the main part of which is the main washing up generator vessel, makes it possible to obtain in reactors with an average neutron flux (from 2 to 5 1017 n / m2 s) generators with a few GBq at acceptable the size of the vessel. The vessels are made before irradiation, when they are inactive. This greatly facilitates manufacturing operations. The design of the main wash-out generating vessel and the tips of the underwater connections provides an easy connection after irradiation under antiseptic conditions. In this way, radiation sterilization can be used simultaneously with neutron activation in the reactor. The generator consists of separate parts, which facilitates its transportation. As an independent part of the kit, it is also possible to supply the main washout generating vessel, which, in view of simple operations, makes it possible to carry out activation in the local reactor.
    Compared to a generator, where the generator’s own column is not activated in the reactor, a certain disadvantage of a new type of generator is the additional activation of the structural material of the main wash-out generator vessel. However, its value is either comparable or lower than the activity of Mo. Therefore, it does not cause significant difficulties in the manufacture of protective containers.
    The combined generator according to the invention brings in comparison with the existing methods of preparing mTS the following advantages:
    15
    20
    the use of reactors with an average neutron flux, easy manipulation of the consumer, simplification of its manufacture, use of spontaneous sterilization during irradiation in the reactor, simplification of transportation due to the possibility of independently sending individual parts of the kit,
    10 easy-to-use in a local reactor, for example, in developing countries by supplying inactive prefabricated parts, including the main washout reactor.
    权利要求:
    Claims (4)
    [1]
    1. An eluent generator of technecy - 99 t, consisting of a generator column filled with activated neutrons, water-insoluble molybdate or polymolybdate, tanks for eluent and eluate connected to the ends of the column, and biological protection, characterized in that the generator column is equipped with a terminal with porous seals and removable closures.
    [2]
    2. The generator according to claim 1, wherein the generator column, protrusions, seals and removable closures are made
    30 of the materials that are weakly activated in the neutron field.
    [3]
    3. The generator according to claims 1 and 2, which differs from the fact that molybdate and polymolybdate contain 20-40 wt.% Molybdenum.
    35
    [4]
    4. A method of manufacturing a technetium-99 elution generator, which includes irradiating water-insoluble molybdate or poly-polybdate and complementing the generator column, characterized in
    40 that molybdate or polymolybdate is placed in the generator column in an inactive form and irradiated with it in a nuclear reactor with a neutron flux of at least 10 n / cm, after which it is attached to the rest of the generator in antiseptic conditions.
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    FR2564634A1|1985-11-22|
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    BG45834A1|1989-08-15|
    GB8512470D0|1985-06-19|
    HUT38003A|1986-03-28|
    引用文献:
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    法律状态:
    优先权:
    申请号 | 申请日 | 专利标题
    CS843764A|CS255601B1|1984-05-18|1984-05-18|99 mtc elution unit-built generator and method of its production|
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